Quantitative determination of UF3 in LiF-BeF2 molten salt system based on XRD internal standard method

被引:0
|
作者
Xu S. [1 ,2 ]
Chen J. [1 ,3 ]
Zou J. [1 ,2 ]
Wang P. [1 ]
Cao C. [1 ]
Lin J. [1 ,2 ]
机构
[1] Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai
[2] University of Chinese Academy of Sciences, Beijing
[3] Guangxi Normal University, Guilin
来源
He Jishu/Nuclear Techniques | 2024年 / 47卷 / 01期
关键词
Internal standard method; Liquid fuel; Quantitative determination; UF[!sub]3[!/sub; X-ray diffraction;
D O I
10.11889/j.0253-3219.2024.hjs.47.010605
中图分类号
学科分类号
摘要
[Background] The conversion of UF6, which is a primary nuclear product, to UF4 in fluoride molten salt phase is expected to be used in the preparation or reconstitution of nuclear fuel salt for molten salt reactors, thus simplifying the process of molten salt reactor fuel production. Determination of the concentration of the key intermediate UF3 plays an important role in obtaining the reaction parameters. [Purpose] This study aims to establish a method for measuring UF3 concentration in solid fluoride molten salts. [Methods] The X-ray diffraction (XRD) was employed to test the homemade standards and obtain the internal standard curve of UF3. Firstly, the α -Al2O3 was taken as the internal standard to obtain the XRD peak height internal standard curve (R=0.986) and peak area internal standard curve of LiF-BeF2-UF3 molten salt. Then, these two internal standard curves were applied to measuring the known content of LiUF5 and UF3 solid mixed samples to compare their accuracies. Finally, measurements were conducted on rapidly cooled LiF-BeF2-UF3 solid molten salt samples and naturally cooled LiF-BeF2-UF3-LiUF5 solid molten salt samples to evaluate the stability and accuracy of the curve, and the relative error was obtained. [Results] In the UF3 concentration range of 1.00~10.00 wt%, the correlation coefficient of the internal standard curve based on the peak area determined for of LiF-BeF2-UF3 molten salt is 0.995. Measuring results of solid mixed samples of LiUF5 and UF3 with known concentrations indicate that the peak area internal standard curve achieves better accuracy with a relative measurement error of no more than 8.7%. In addition, the results of the same content samples with different cooling methods confirm the good stability and accuracy of the proposed method with less than 5.4% relative standard deviation. [Conclusions] The established method can be used for the quantitative analysis of solid LiF-BeF2-UF3 and LiF-BeF2-UF3-LiUF5 molten salts with good measurement accuracy and repeatability. © 2024 Science Press. All rights reserved.
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  • [1] Yang X, Guo L H, Zhang F, Et al., Microstructure and mechanical properties evolution of thermal-treated SiC layer with fine grain size in TRISO particles, Materials Science and Engineering: B, 287, (2023)
  • [2] Guo L H, Zhang F, Lu L Y, Et al., Preparation of the highly dense ceramic-metal fuel particle with fine-grained tungsten layer by chemical vapor deposition for the application in nuclear thermal propulsion[J], Tungsten, 4, 1, pp. 1-9, (2022)
  • [3] Yang X, Zhang F, Guo M S, Et al., Preparation of SiC layer with sub-micro grain structure in TRISO particles by spouted bed CVD[J], Journal of the European Ceramic Society, 39, 9, pp. 2839-2845, (2019)
  • [4] Merle-Lucotte E, Heuer D, Allibert M, Et al., Introduction to the physics of molten salt reactors[C], Materials Issues for Generation IV Systems, pp. 501-521, (2008)
  • [5] Serp J, Allibert M, Benes O, Et al., The molten salt reactor (MSR) in generation IV: overview and perspectives[J], Progress in Nuclear Energy, 77, pp. 308-319, (2014)
  • [6] YU Kaicheng, CHENG Maosong, DAI Zhimin, Development and verification of fuel management code for liquid-fueled molten salt reactor based on deterministic code system, Nuclear Techniques, 44, 4, (2021)
  • [7] SUN Guomin, CHENG Maosong, DAI Zhimin, Preliminary analysis of fuel management for a small modular molten salt fast reactor, Nuclear Techniques, 39, 7, (2016)
  • [8] JIANG Mianheng, XU Hongjie, DAI Zhimin, Advanced fission energy program - TMSR nuclear energy system, Bulletin of the Chinese Academy of Sciences, 27, 3, pp. 366-374, (2012)
  • [9] WANG Peng, ZHENG Haiyang, SHE Changfeng, Et al., Electro-deposition method for uranium trifluoride
  • [10] WANG Peng, SUN Lixin, CAO Changqing, Et al., Method for reconstructing molten salt reactor fuel: CN109637682 B